Assessment Of Occupational Radiation Exposure Research Articles

Assessment of occupational radiation exposure during a specific endoscopic retrograde cholangiopancreatography procedure.

The aim of this study was to evaluate the occupational radiation exposure of staff during endoscopic retrograde cholangiopancreatography (ERCP), with a focus on individuals closest to the radiation source, and to identify potential increases in exposure to hands and eye lenses. Patient radiation exposure during ERCP was also assessed. Staff organ doses were monitored using a Philips Allura Xper FD 20 fluoroscopy system, during 24 ERCP procedures for a period of 7months. Staff doses were measured using thermoluminescence dosemeters and electronic personal dosemeters, and patient effective doses were simulated and calculated. Physicians' annual organ doses ranged from 0.2 to 1.6mSv for shoulders, 0.1 to 0.4mSv for eye lenses, and 0.3 to 1.6mSv for fingers. The annual organ dose of the nursing staff ranged from 0.08 to 2.4mSv for shoulders, 0.02 to 2.3mSv for eye lenses, and 1.2 to 5.3mSv for fingers. The effective dose to patients ranged from 0.009 to 0.46mSv. Staff doses were within safe limits, but patient doses were high, emphasizing the need for improved radiation protection.

Quantitative assessment of occupational radiation exposure in CT: a comparative study using two radiation survey meters for year-long dose monitoring of staff

Introduction: Computed Tomography (CT) is crucial in medical imaging but exposes healthcare workers to ionizing radiation. It is essential to quantify and mitigate occupational radiation exposure. This study provides a comprehensive quantitative analysis of CT settings, using two radiation survey meters, over a year-long monitoring period. Methodology: Healthcare workers operating CT scanners were included. Two radiation survey meters, Meter A (GMC-300E, uSv/h) and Meter B (RAR R311516, uSv/h), were used concurrently for continuous measurement and recording of radiation doses. Statistical analysis compared data from both meters and assessed compliance with regulatory limits and quality assurance standards. Results: The study demonstrated excellent consistency in dose measurements between Meter A and Meter B throughout the year, with no statistically significant discrepancies (p≤; 0.05). Cumulative radiation doses of staff remained within legal limits, indicating the efficacy of current safety measures. Conclusion: The study highlights the reliability of Meter A and Meter B for measuring occupational radiation exposure in CT settings. The convergence of results emphasizes their suitability for healthcare settings requiring precise radiation dose monitoring, enhancing radiation safety in CT scanning and protecting healthcare personnel from ionizing radiation exposure.

Assessment of Occupational Radiation Exposure for Radiotherapy Healthcare Workers at Kenyatta National Hospital Using Thermoluminescence Dosimeter LiF:Mg,Ti

Assessment of Occupational Radiation Exposure for Radiotherapy Healthcare Workers at Kenyatta National Hospital Using Thermoluminescence Dosimeter LiF:Mg,Ti

Assessment of occupational radiation exposure of NORM scales residues from oil and gas production

Radiological hazards from external exposure of naturally occurring radioactive materials (NORM) scales residues, generated during the extraction process of oil and gas production in southern Algeria, are evaluated. The activity concentrations of 226Ra, 232Th, and 40K were measured using high-purity gamma-ray spectrometry (GeHP). Mean activity concentration of 226Ra, 232Th and 40K, found in scale samples are 4082 ± 41, 1060 ± 38 and 568 ± 36 Bq kg−1, respectively. Radiological hazard parameters, such as radium equivalent (Raeq), external and internal hazard indices (Hex, Hin), and gamma index (Iγ) are also evaluated. All hazard parameter values were greater than the permissible and recommended limits and the average annual effective dose value exceeded the dose constraint (0.3 mSv y−1). However, for occasionally exposed workers, the dose rate of 0.65 ± 0.02 mSv y−1 is lower than recommended limit of 1 mSv y−1 for public.

Occupational radiation exposure assessment during the management of [68Ga]Ga-DOTA-TOC

BackgroundSince it was first approved in Europe in 2016, the gallium-68 (68Ga) radiopharmaceutical [68Ga]Ga-DOTA-TOC has been widely used for imaging of somatostatin receptor (SSTR) positive tumours using positron emission tomography–computed tomography (PET/CT). Significant patient benefits have been reported, so its use is rapidly increasing. However, few studies have been published regarding occupational doses to nuclear medicine personnel handling this radiopharmaceutical, despite its manual usage at low distances from the skin and the beta-emission decay scheme, which may result in an increased absorbed dose to their hands. In this context, this study aims to analyse the occupational exposure during the administration of [68Ga]Ga-DOTA-TOC for PET/CT imaging. For this purpose, extremity, eye lens and whole-body dosimetry in terms of Hp(0.07), Hp(3) and Hp(10), respectively, was conducted on six workers with both thermoluminescent dosimeters, and personal electronic dosimeters.ResultsThe non-dominant hand is more exposed to radiation than the dominant hand, with the thumb and the index fingertip being the most exposed sites on this hand. Qualitative analysis showed that when no shielding is used during injection, doses increase significantly more in the dominant than in the non-dominant hand, so the use of shielding is strongly recommended. While wrist dosimeters may significantly underestimate doses to the hands, placing a ring dosimeter at the base of the ring or middle finger of the non-dominant hand may give a valuable estimation of maximum doses to the hands if at least a correction factor of 5 is applied. Personal equivalent doses for the eyes did not result in measurable values (i.e., above the lowest detection limit) for almost all workers. The extrapolated annual dose estimations showed that there is compliance with the annual dose limits during management of [68Ga]Ga-DOTA-TOC for diagnostics with PET in the hospital included in this study.ConclusionsImaging with [68Ga]Ga-DOTA-TOC is a safe process for the workers performing the administration of the radiopharmaceutical, including intravenous injection to the patient and the pre- and post-activity control, as it is highly unlikely that annual dose limits will be exceeded if good working practices and shielding are used.

Assessment of occupational radiation exposure among medical staff in health-care facilities in the Eastern Province, Kingdom of Saudi Arabia.

Introduction:Radiation exposure poses hazards for health-care providers as well as patients in health-care facilities (HCFs). Radiographic imaging is extremely valuable as a diagnostic tool in medicine, but ionizing radiation and computed tomography (CT) scan carry well-known potential risks. Personnel and radiation safety monitoring is an important safety precaution in the practice of radiography.Aim:The study aimed to assess the occupational radiation exposure and safety protection among medical staff in HCFs in the Eastern Province, Kingdom of Saudi Arabia (KSA).Materials and Methods:Total of 4 HCFs with radiological services were randomly selected for the study in the period from January to April 2013. The radiation survey has been carried out by the measurement of radiation in the x-ray and CT-scan room at different points of the diagnostic, imaging, and waiting rooms of different hospitals. The radiation safety was assessed by using a questionnaireResults:The results of our study are surprising and alarming. Data revealed that there are a significant association between the levels of radiation exposure in all selected hospitals concerning imaging and waiting X-ray and CT-scan operating room (P < 0.01). For radiation safety, most hospitals have lead aprons and thyroid shields in place, but only about 50% have lead glasses and lead shields, showing that many hospitals still lack essential equipment. Moreover, actual utilization rate of radiation dosimeters are 57.7% and 68.9%, respectively.Conclusion:All medical staff as well as patients are at risk of exposure to x-ray and CT-scan radiation exposure, and the levels are exceeding the standard guidelines. Many hospitals still lack safety protection tools and there is a complete absence of radiation protection equipment. Further studies should be conducted to highlight different aspects of radiation exposure dose and safety protection tools.

Assessment of occupational radiation exposure in underground artisanal gold mines in Tongo, Upper East Region of Ghana

Assessments of radon and gamma radiation levels were carried out in underground artisanal gold mines in Tongo. This is one of the numerous artisanal gold mining communities in Ghana. Solid State Nuclear Track Detectors (SSNTDs) were used to estimate the mean 222Rn concentration and dose rates during the Harmattan season (November 2010 to February 2011). The values for the 222Rn concentration at each monitoring site ranged from 14 ± 4 Bq m−3 to 270 ± 9 Bq m−3, with a mean value of 98 Bq m−3. These measurements are well below the lower action level of 500 Bq m−3 recommended by ICRP for workplaces. The activity concentrations of 40K, 232Th and 238U were determined using gamma-ray spectroscopy method. The effective dose estimates of 0.11 ± 0.02 mSv y−1 to 0.68 ± 0.04 mSv y−1 were below the allowable limit of 20 mSv per annum for occupational exposure control recommended by the ICRP. The total annual effective dose varied from 0.22 ± 0.04 mSv y−1 to 1.92 ± 0.08 mSv y−1.

Assessment of occupational radiation exposure (ORE) for hands-on assistance to the remote handling at ITER ports and waste treatment

The occupational radiation exposure (ORE) assessment for ITER systems is evolving as design makes progress. This paper deals with the ORE assessments for two important ITER activities: those in the assistance to the remote handling on a port plug hosting diagnostics and those carried out in the Waste Treatment System. For the former a software tool has been developed to handle the large amount of data processed and to allow user friendly updating of data as design or maintenance procedures evolves, and, know-how on maintenance activities improves. A systematic approach was adopted to evaluate work efforts (WE) needed to execute specific tasks. The so-called “elementary works” were identified and classified and the time required to perform the operation and involved people were estimated. The elementary works were then aggregated in the so-called main operations (e.g. window replacement, pipe removal, etc.). For each of them, on the base of expected maintenance frequency and dose rate fields, total WE and worker doses were calculated. It was assessed that hands-on activities in the Equatorial Port No. 1 require 472 person h of WE leading to a collective dose of ∼7.4 person mSv/year. The most critical operation in terms of worker doses is the sealing/unsealing of port plug, which weights for about the 23% of the total. The second ORE assessment was related to the management of ITER operational radioactive wastes. These wastes include streams originated in the plant from the experimental and maintenance activities, with exclusion of those generated inside the Tokamak that will be highly activated and will be managed inside the Hot Cell Processing System. The estimated collective annual dose related to the Waste Treatment System ranges between ∼4.3 and ∼4.9 person mSv. The two values depend on the assumptions made for the exposure levels in the operative areas. Both studies have to be considered as preliminary as far as the results are concerned due to the quite rough input data (on dose rates and design details), while the approach might be considered sound and up to date.

Assessment of occupational radiation exposure for two fusion power plant designs

An assessment of the occupational radiation exposure issues of the fusion power stations has been performed focusing on the primary heat transport system (PHTS) of safety and environmental assessment of fusion power (SEAFP) reactor models. Fuel cycle systems have been considered for completeness, but not assessed. Fission reactor experience and fusion power reactor studies formed the basis of this assessment. Four assessments were performed. Two were based on SEAFP models 1 and 2, and the other two were based on improvements of these models suggested by an as low as reasonably achievable (ALARA) review. The following main conclusions are drawn from the assessments. The PHTS dose estimated for SEAFP model 1 (about 300 p-mSv/a) is below the current fission industry norm (about 500 p-mSv/a), but it is not ALARA. An ALARA value of 130 p-mSv/a is achievable and would be a reasonable target for the PHTS. The PHTS dose estimated for SEAFP model 2 (about 3000 p-mSv/a) is well above the current fission industry norm. Some design measures have been identified, that can reduce this dose to about 1200 p-mSv/a. While this is a substantial reduction, it is still well above the fission industry norm, therefore, additional effort is needed to obtain further reductions. The large difference in heat transport system doses between model 1 and model 2 is due to two main factors, the coolant and the coolant tubing material. The helium coolant eliminates the presence of corrosion products, and the vanadium alloy reduces the sputtering rate.